ML20039C407
| ML20039C407 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/22/1981 |
| From: | Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-50-328-81152, NUDOCS 8112290323 | |
| Download: ML20039C407 (1) | |
Text
TELECOPY TO NRC DEC 221981 REGIONAL DIRECTOR DEPUTY DIRECTOR 3
ASSISTANT TO DIRECTOR
~T U.S. Noclear Pagulatory Commission
~ ' '
DIRECTOR, RRPI Z
Fagion II DIRECTOR, EPOS lot Marietta street, ta suite 3100 DIRECTOR, ENF/INV
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Atlanta, Georgia 30303 DIRECTOR, ETl T
PUBUC AFFAIRS OFFICER SQEO-50-328/Sil52
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Reported Doder Technical Specification 6.9.1.12.b J
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Date of Occurrence:
12/22/81 Time of Occurrencer 0300 CS1 D{g g g yg3I Teclutical Specification Involved:
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Conditions Prior to Occurrence
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N Unit 2 in mode 2, 07, power, RCS temperature and pressure 547 degrees'7 snd 2235 psig.
Identification and Description _of Occurrence _
While increasing reactor parameters for power ascension, control rod withdrawal limits established in accordance with the action statement associated with limiting condition for operation 3.1.1.3 of the Sequoyah Technical Specifications were violated. These operating limits were established as required by LCO
- 3. L. I.3 in Special Report 81-4 sent to !&. James P. O'Reilly on Novmber 13, 1981.
_ Apparent Cause of Occurrence The operating limita established were not la startsp procedures, and the time peribd since November 13, 1981, contiibuted to the inadvertent omission of referencing the operating limits to maintain a negative moderator temperature coef ficient during Voit 2 startup.
Other Related Events-P4ference the memorandum and enclosed Special Report front H..L Green to Ik, James P. O'Reilly dated November 13, 1981.
Corrective Action Taken or Planned The operator diluted the boron concentration in order to reestablish applicable control rod positions to within established operating limits within an hour.
A temporary change is being proposed to our Technical Instruction 21 (Calculation of Estimated Critical Conditions) with a note to caution the unit operatora un established control rod withdrawal Itmits.
p C. C.14ason j g Power Plant Superintendent secuovah Nuclear Plant 8112290323 811222 PDR ADOCK 05000328 S